Papers by Keyword: Reactor Safety

Abstract: In order to obtain license renewal for RSG-GAS operation expired in 2020, an evaluation on periodic safety review (PSR) should be performed as required by BAPETEN regulation. This PSR had been done from 2005 to 2015. The objectives of the qualification review is to ensure that the critical structure, system, and component (SSC) for safety fulfils the requirements. SSC, which is important to safety, is reviewed in term of its environment, service frequency, aging mechanism, aging mitigation, and aging degradation detection. The results of this detection are evaluated to achieve sustainable and safe operation and to identify SSC replacement and repair before a failure occurs. From the evaluation results, it can be concluded that SSC qualification during the period of 2005 – 2015 still fulfils the requirements so that safe and sustainable operation of RSG-GAS is assured.

Abstract: Investigating nuclear power plant containments under accidental conditions obviously leads to the question of possible leakage through cracks of the pre-stressed concrete containment. In the last decades a number of civil engineering R&D programs dedicated to theoretical and experimental analyses have been performed. For the PACE-1450 experiment a leakage testing facility for pre-stressed curved specimen has been built in the laboratory of the Materials Testing and Research Institute (MPA Karlsruhe) at the Karlsruhe Institute of Technology (KIT). The test campaign has now been successfully finished with the evaluation of gained results still ongoing. The first half of the campaign was mainly dedicated to the cracking of the realistically reinforced specimen while the second half was focussing on the leakage behaviour of the cracked specimen. In the tests cold air, heated air and air-steam mixtures were used.

Abstract: It is common for the most reactor pressure vessel (RPV) of light-water reactors used today, that the RPV made of ferrite-perlitic steel is cladded with an austenitic layer, which well resists corrosion influence. The cladding is manufactured by welding, the technology (mode of application, number of layers) is different by each manufacturer. This is the layer which comes into contact with the working media first, and is of course in cohesive contact with the RPV material. The aim of this study is to demonstrate the new approach, used for assessing the safety of the reactors today. This approach plays a decisive role in the lifespan calculation of already operating nuclear power stations, including the extension of their service period.